Text

Exam Rept 50-089/Ol-90-01 on 901023-24.Exam Results:One Senior Reactor Operator (RO) & One RO Passed Exam
	ML20062G293
Person / Time
Site:	General Atomics
Issue date:	11/08/1990
From:	Meadow T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
Shared Package
ML20062G281	List: ML20062G280; ML20062G293; ML20062G314;
References
	50-089-OL-90-01, 50-89-OL-90-1, NUDOCS 9011290093
	Download: ML20062G293 (56)
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' Enclosure 1

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Examination Report.'No. 50-89/0L-90-01 O

9 Facility:

General Atomics 9

Examinations administered at the Generali Atomics, Torrey Pines Facility, San Diego, California.

Eyaminer:

Richard J. Laufer, Chief Examiner' Approved:

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,v/v/v Thomas R. Meadows, Acting Chief Date, Signed Operations Section Summary:

Examinations from October 23 through October-24, 1990, (Report No. 50-89/0L-90-01)

Operator licensing examinations were administered to one. Reactor 0perator (RO)

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and one Senior Reactor Operator (SR0) candidate.

Both of these candidates passed their examinations and were subsequently. issued licenses.

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9' 9011290093 901108 PDR ADOCK 0500 9

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REPORT DETAILS 1.

Examiners Richard J. Laufer, HQ, Chief Examiner 2.

Persons attendino the Exit Meeting on October 24, 1990 Richard Laufer, HQ Chief Examiner

Junaid Razvi, Manager, ikIGA Reactors Facility

William Whittemore, Senioi Scientific Advisor, TRIGA Group

Attended the written examination review on October 24, 1990.

3.

Written Examination ai.d Fac @ y Review f

The n examinat:s

.os admenistered-tosthe R0_ candidate on Octot -

, 1990 at che General Atomics, Torrey Pines Reactor Facility. At:.the conclusion of the. examination the Chief Examiner held a formal review with the facility staff identified in paragraph (2) above, in accordance with NUREG 1021 The'0perator Licensing i

Examiner Standards. The NRC resolutions of_these comments are documented in Enclosure (3) of this report, which includes the; licensee's formal record of this meeting [ Attachment. A to Enclosure (3)].

The R0 candidate passed this portion of his examination.

4.

Operating Examinations The operating examinations.were administered on October 23-24, 1990.

These examinations were conducted using walk-through scenarios-that-tested the operator candidates' integral. system knowledge and ability to actually operate the reactor facilities. Aspects of facility design and control, administration, security,,agd emergency plan-were also -

thoroughly tested.

Both operator candidates passed the operating portion of their examinations.

5.

Exit Meeting On October 24, 1990, the Chief Examiner met with the representatives of the licensee's staff to discuss the examination.

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WRITTEN EXAMINATION FACILITY COMMENTS /NRC RESOLUTION OF COMMENTS (R0 EXAMINATION)~

l Question'A.011:

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Comment:

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"The" correct" answer (perexamkey)is(b)andisonlyobtainedbyusingan approximation to the in-hour equation.

However, since the 1n-hour curve was also provided to the candidate, obtaining)'the stable period from the curve is also acceptable; this makes answers (c and (d) closer to the correct value of stable reactor period. Therefore, answer (b), (c), and (d) are all l

acceptable, since the method of obtaining the period was not_ specified to the candidate."

l NRC Resolution:

Comment not accepted. The wording of the question, by giving the candidate I

assumed values of Lambda-eff and B-eff, implies that a calculation is required.

The wording of this question will be further clarified before uploading it to.

l the exam bank.

t l

Question 8.008:

Comment:

"We suggest the wording of the question be changed to '... remain in MANUAL mode when the operator depresses the PULSE mode pushbutton?'

This is to clarify the fact that for pulsing the reactor, the ooerator must first switch to pulse mode, then depress the pulse Fi?.E pushbutton, We are in agreement with the answer given in the answer, key."

NRC Resolution:

Comment noted. The wording of this question will be modified prior to uploading to the exam bank.

t Question C.001:

Comment:

i "This cuestion should be deleted.

None of'the answers apply. This was l

verified in the training manuals."

NRC Resolution:

Comment accepted. The Chief Examiner concurred that a mistake had been made in transcribing data from the reference material. Therefore, this question has been deleted frcm the examination.

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Question C.013:

Comment:

"Twooftheanswersareequallycorrect-(a)and(b). One of the two answers is not discussed in the training materials because~the UPS on the Mark I reactor is a recent addition to the facility. We accept this oversight. However, if the candicate gave either (a) or (b)-as the correct answu,' then it shot.1d be acce)ted. The addition of the UPS to-the Mark I was pointed out to the examiner in tie walk through."

NRC Resolution:

Comment accepted. Due to incomplete facility reference material this question-has two correct answers.

Bothanswers(a)and(b)willbeacceptedascorrect answers.

Question C.016:

Comment:

i "Two answers - (b) and (d), are correct.

This was verified in the training materials, i

NRC Resolution:

Comment accepted. Both answers (b) and (d) will be accepted as-correct answers.

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NqCOfficialU2 Only

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Nuclear Regulatory Commission Operator Licensing Examination I

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1 This document is removed from Official Use Only category on date of examination.

NRC Official Use Only wr w

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y U. S. NUCLEAR REGULATORY. Cotti!SSION MASTTA CAPT l

NON-PDWER REACIOR LICENSE EXAMINATION l

i FACILITY:

General Atomic Co.

REACIOR TYPE:

TRIGA-I/F DATE ADMINISTJRED:

90/10/23 i

RECION:

5 CANDIDATE:

i LICENSE APPLIED FOR:

i INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the exam page itself, or the answer-sheet provided. Write answers one side ONLY.- Attach any answer sheets to the examination.

Points for each question are indicated in parentheses for each question. A 70% in each section is required to pass the examination.

Examinations will be picked ~up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00

.r. 20

A.

REAUTOR THEORY, THERMODYNAMICS 31 'f' AND FACILITY OPERATING CHARACTERISTICS B.

NORbALANDEMERGENCYOPERATING

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20.00 4:936 36 i'

- PROCEDURES AND RADIOIDGICAL CONTROLS

-WOOA M C.

PLANT AND RADIATION MONITORING

19. 0 0 5 t to SYSTEMS M

TOTALS s9.00 8

FINAL GP.ADE All work done on this examination is my own.

I have.neither given nor received aid.

Candidate's Signature

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n NRC RULES AND GUIDELINES FOR LICERSE EXAMINATIONS g

During the administration of this examination the _ following rules apply

1. Cheating on the examination means an automatic denial of your application

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and could result in more severe penalties.

2. After the esamination has been completed, you must sign the statement on-the cover sheet indicating that the_ work is-your own.and you have not received or given assistance in completing the examination.

This 'must be done after you complete the examination.

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3. Restroom trips are to be limited and only one candidate atia time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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4. Use blaci ink or dark pencil only to facilitate legible reproductions.

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5. Print youi name in the blank provided in the~ upper right-hand corner of the e. amination cover sheet.

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6. Use only the answer sheets provided. Credit will only be given for answers properly marked on these sheets.

Follow the instructions for tilling out E

the answer sheets.

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7. Print your name in the upper right-hand corner of e i-answer sheet.

8. Partial credit will NOT be given on multiple choice questions.

9 If the intent of a question is unclear.ask questions of the examiner only.

10. When turning in your examination, assemble the completed examination with examination questions, examination aids:and answer sheets.

In addition, turn in all scrap paper.

11. To pass the examination, you must achieve at least 70*4 in each category.

12. There is a time limit of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months for completion of the examination.

13. When you are done and-have turned in your e4 amination, leave the examin-ation area as defined by tha examiner.

1'you are found in this area while the examination is still in progress, yo'.r licenso'may be denied or revoked.

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RX THEORY, THERM 0 b FAC OP CHARS

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s QUESTION: 001 (1.00)

Which one of the following terms is described as the total number of fast neutrons compared to the number in the original group?

a.

resonance escape probability 1

b.

fast fission factor i

c.

fast non-leakage probability d.

reproduction. factor QUESTION: 002 (1.00)

Which one of the following factors is most easily varied by the reactor operator?

j a.

reproduction factor b.

fast fission factor c.

fast non-leakage probability d.

thermal utilization factor 1

QUESTION: 003 (1.00)

Which one of the following is the correct reason that delayed neutrons enhance control of the reactor?

More delayed neutrons are produced than prompt neutrons.

a.

b.

Delayed neutrons increase the mean neutron lifetime.

Delayed neutrons take longer to thermalize than prompt neutrona.

c.

d.

Delayed neutrons are born at higher energies than prompt neutrons.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

t-A..RX THEGF D & FAC'OP CHARS

{

Page 51

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s' QUESTION: 004 (1.00)

Which one of the fo110"L.ig conditions describes a reactor that is exactly critical?

a.

Keff : 1: delta-K/K = 0 b.

Keff = 1; delta-K/K = 1 c.

Keff : 0; delta-K/K = 0 d.

Keff = 0: delta-K/K = 1 QUESTION: 005 (1.00)

With Keff = 0.987, how much reactivity must be added to-make the reactor critical?

a.

1.30% delta-K/K b.

1.32% delta-K/K c.

1.34% delta-K/K d.

1.36% delta-K/K QUESTION: 006 (1.00)

A suberitical reactor has an initial source range count rate of 150 cps with a shutdown reactivity of -2.0% delta-K/K. How much positive reactivity must be-added to establish a stable count rate of 300 nps?

a.

0.5% delta-K/K b.

1.0% delta-K/K c.

1.5% delta-K/K d.

2.0% delta-K/K

(***** CATEGORY A CONTINUED ON NKXT PAGE *****)

t;.,RX THEORY. THERMO & FAC OP CHARS Page 6 QUESTION: 007 (1.00)

While withdrawing control rods during an approach to criticality, the count rate doubles. What will occur if the same amount of reactivity that caused the first doubling is added again?

a, count rate will increase slightly b,

count rate will double c.

the reactor will remain suberitical d.

the reactor will be critical or slightly supercritical QUESTION: 008 (1.00)

Two identical reactora are c;4 rating et power. Reactor "A" is at 1 MW and reactor "B" is at 100 KW, If both reactors scram at the same tie. xenen-135 will peak first in reactor and the highest xenon-135 reactivity peak will occur in reactor a.

"A"; "A" b.

"A"; "B" c.

"B"; "A" d.

"B"; "B"

(***** CATEGORY A 00NTINUED ON N2XT PAGE *****)-

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,RX THEORY. THERMO & FAC OF CWdtS

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t QUESTION: 009 (1.00)

Which one of the following statements correctly states how neutron f1to: is effected by the addition of a reflector around a reactor core?

a.

With a reflector in place thermal flux is higher at the edge of the Core.

b.

With a reflector in place thermal flux is lower at the edge of the core.

c.

With a reflector in place fast flux is higher at the edge of the ccre.

d.

With a reflector in place fast flux is lower at the edge of the core.

QUESTION: 010 (1.00)

With the reactor at a power of 10 watts and a period of 20 seconds,'how long will it take for power to reach 1 KW7 L.

41 seconds b.

69 seconds c.

92 seconds

d. 11:

sconds QUESTION: 011 (1.00)

The Mark I reactor is at a power of 0.1 watt and 25 cents of reactivity is added.

What is the resulting stable reactor period? (Assume lamda-eff = 0.08 and Beff

= 0.007) a.

48 seconds b.

36 seconds c.

28 se;onds d.

22 seconds

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

s A.,RX THEORY. THERMO & FAC OP CHARS l

Pags 8

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h QUESTION: 012 (1.00)

The Mark F reactor is suberitical with a Keff of 0.96 and 30 eps indicated.

After a fuel element is removed the count rate drops to 10 cps. No other changes have occurred. What is the Keff of the core with the fuel element removed?

a.

0.9733 b.

0.8800 c.

0.8400 d.

0.6666 QUESTION: 013 (1.00)

The Mark F reactor uses as its reflector and the Mark 1 uses a.

water; graphite b.

zirconium; water c.

graphite; water d.

watsr; aluminum QUESTION: 014 (1.00)

~~

Which one of the following is a reason for using Graphite Dummy Elements in the TRIGA core?

a.

to provide additional shielding b.

to absorb neutrons that would otherwise leak from the core c.

to reduce the fuel element requirements d.

to reduce the thermal flux at the core boundary

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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RX THEORY, THERMO & FAC OP CHARS l

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s QUESTION: 015 (1.00) 1 Which one of the following statements describes a reactor's excess reactivity?

a.

The amount of reactivity needed to achieve criticality.

l b.

The amount of reactivity required to shut.the reactor down.

c.

The amount of reactivity available above that which is required to keep the reactor suberitical, d.

The amount of reactivity available above that which is required'to keep the reactor critical.

QUESTION: 016 (1.00)

Which one of the following is one of the advantages of the neutron source used in the Mark F reactor?

a.

It can be reactivated by power operation of the reactor, b.

It has a relatively long half life, c.

It has a relatively short half life, d.

It has a large gamma ray yield.

(***** CATEGORY A CONTINUED ON NEXT PAGE **t**)_

A,.

, kX THEORY, THERMO & FAC OP (HARS i

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k QUESTION: 017 (1.00)

Which one of the following statements correctly describes the effect of a fuel ttmperature increase on a fuel-moderr. tor element?

The probability that a thermal neutron will loee energy in a collision a.

with an excited sta' Hydrogen atom increases.

b.

The probability tha, s neutron will escape from the element before being captured significantly increases.

c.

The thermal neutron spectrum in the fue. element shifts to a lower average energy.

d.

The mean free path for neutrons in the element is decreased appreciably.

QUESTION: 018 (1.00)

Which one of the following is the reason that power decreases on.the same stable negative period following a reactor scram regardless of the initial power level?

i The rate of power change is dependent on the mean lifetime of the a.

longest lived delayed neutron precursor, b.

The rate of power change is dependent on the constant decay rate of prompt neutrons, The rate of power change is dependent on the mean lifetime of the c.

shortest lived delayed neutron precursor.

d.

The rate of power change is dependent.on-the constant decay rate of prompt gamma emit,ers.

9

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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

l A.,t.A 'Antun1. 'inttm & the UP criAxs l

page 11

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QUESTION: 019 (1.00)

Using the heat flux curve pictured below, select the region of the curve where the TRIGA reactor core cooling normally occura, i

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te; At a.

region I b.

region II c.

region III d.

region IV

. i

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(***** CATEGORY A CONTINUED ON NEXT-PAGE *****)

\\

w w

w'

q A..RX THEORY, THEPJ10 & FAC OP CHARS i

Paga 12

\\i QUESTION: 020 (1.00)

A Triga reactor is being loaded for criticality. The following tabulation summarizes the number of elements added and the resulting steady. state count rate. The source level (Ro] is considered to be 1000 CPM.

(R/Ro : count rate / source 1e el).

NO. OF ELEMENTS COUNT RATE (CPM)

R/Ro Ro/R 50 3000 3.00 0.333 55 4255 4.25 0.235 60 7000 7.00 0.143 Which one of the following is the number of fuel elements that will be require,d for critica111ty?

a.

57 b.

62 c.

67 d.

72 l

1 l

l l

l 1'

-(***** END OF CATEGORY A *****)-

3

. B.

, NORMAL /EMERG PROCEDURES & RAD CON

[

P0ge 11

\\L h

QUESTION: 001 (1.00)

An accessible area with a radiation level of 75 mrem /hr should be posted as a(n) a.

restricted area b.

radiation area t

c.

high radiation area d.

radiologically controlled area QUESTION: 002 (1.00)

Prior to returning to tower following an unplanned or unscheduled shutdown, the Rsactor Operator must obtain the approval of the a.

Senior Reactor Operator l

b.

Acsociate Physicist-in-Charge c.

Physicist-in-Charge d.

Criticality Safeguards Committee l

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

o B.. NORMAL /EMERG PROCEDURES & RAD 00N i

Pags 14

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4 QUESTION: 003 (1.00)=

A modified routine experiment is to be performed and it has been detemined and documented that the hazards associated with the experiment are neither cignificantly different nor greater than the corresponding referenced routine.

cxperiment.

Which one of the following individuals or groups'is required to approve the Ierformance of the modified routine experiment described above?

a.

SRO b.

Associate Physicist-in-Charge c.

Physicist-in-Charge d.

Criticality Safeguards Committee QUESTION: 004 (1.00)

The Reactor Start up Checklist is required to be performed in which one of the' following cases?

a.

prior to all reactor start ups b.

prior to each day's reactor operations c.

only prior to the start up of an operation expected to.last more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months d.

only prior to the start up following a shutdown of greater than 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

(**r** CATEGORY B CONTINUED ON NEXT PAGE *****)

l l

l 1

1

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. B.

. NORMAL /EMERG PROCEDURES'& RAD 00N Pags-16

[

N.

\\

QUESTION: 005 (1.00)

Maintenance work which requires the manual movement of a control rod is scheduled to be accomplished on your shift. Which one of the following is a requirement that must be met or verified in order to perform such maintenance?

\\

a.

The reactor will be shutdown with the rod being worked on' removed from the core.

b.

The worth of the shutdown rods in the core is at least two times the available excess reactivity, c.

The work must be performed by a licensed SRO.

d.

The magnet' power supply to all rode must be turned off.

~

3 QUESTION: 006 (1.00)

Which one of the following correctly describes the dosimetry that would be r2 quired to be worn by a sixteen year old boy who was touring the reactor ftcility as part of a large group?

a.

The boy would not be issued dosimetry or be allowed to tour the facility since he is under 18 years of age.

b.

The boy would be required to wear a pocket dosimeter.

c c.

The boy would not need any dosimetry as long asLat-least one dosimeter was issued for every five persons in the group, d.

The boy would be required to wear a film badge or TLD.

t

(***** CATEGORY B CONTINUED ON NEXT PAGE '*****)

i

v

-.B.

.!30PJiAL/EMERG PROCEDURES & RAD 00!l I

Paga 16

\\

h QUESTION: 007 (1.00) i According to the Mark I Reactor Start up Procedure, if all systems are operating properly, core excess should be determined at a power level less than l

l a.

100 W b.

1 KW e.

3 KW d.

6 KW QUESTION: 008 (1.00)

Which one of the following conditions will cause the Mark I Reactor Control System to remain in MANUAL mode after the PULSE button is depressed?

a.

reactor power is 750 W b.

the transient rod is all the way down c.

air is applied to the transient rod drive d.

reactor period is 30 seconds QUESTION: 009 (1.00) l l

Which one of the following is the reason that the conductivity of the pool water in required by Technical Specifications to be maintained less than or equal.to 5 umho/cm?

l a.

to enhance the effectiveness of the demineralizer at removing ions L

b.

to more easily detect an abnormal increase in ion concent ation c.

corrosion of reactor. components is minimized at lower cor:ductivity levels d.

a higher conductivity level would change the moderating effect of tha water

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

~ M B.

,NURP1AL/tt! EMU FXUUtWXb5 & hAU UUN j

rage ai

\\

QUESTION: 010 (1.00)

How long can you work in an area with a general background radiation. level of 250 mr/hr before you would exceed the minimum 10 CFR 20 whole body' quarterly limit?

a.

3.0 hours0 days 0 hours 0 weeks 0 months b.

5.0 hours0 days 0 hours 0 weeks 0 months c.

7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months d.

10.0 hours0 days 0 hours 0 weeks 0 months i

4 QUESTION: 011 (1.00)

A point source of gamma radiation measures 50-mr/hr at a distance of 2 feet.

Assuming 100% detector efficiency for gamma, what will the exposure rate be at a distance of 16 feet from the sourca?

a.

0.625 mr/hr b.

0.78 mr/hr r

c.

6.25 mr/hr 1

d.

7.8 mc/hr

- i i

+

i

(***** CATEGORY B CONTINUED ON'NEXT PAGE *****).

B,. e NORMAI,/EMEEG PROCEDURES & RAD CON -

Pege 18-QUESTION: 012 (1.00)

During a Reactor Power Calibration on the Mark I Reactor the % error on one channel is 5%. Which one of the following adjustments must be made to correct this error?

a.

No adjustment is necersary unless cne % error is greater than or equal to 7%.

b.

The gain of the neutron Cetector must be adjusted to match-the measured thermal power.

c.

The neutron detector compe.tsating voltage must be adjusted to match the measured thermal output.

d.

The neutron detector height must be adjusted to match'the measured thermal output.

i QUESTION: 013 (1.00)

According to the Mark I Reactor Technical Specifications, which ons of the following individuals is authorized to make temporary changes to proesdures that do not change the original intent of the procedure?

a.

Senior Reactor Operator on duty-b.

Associate Physicist-in-Charge c.

Physicist-in-Charge d.

Criticality Safeguard-nmittee Chairman 1

In

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

a.,

B,. NORMAL /EMERG PROCEDURES & RAD CON l

P:go 19 l

\\

t l

r QUESTION: 014 (1.00)

A2ide from a licensed RO on each reac',or, which one of the following describes l

the additional personnel required to meet the minimum manning requirements with 1

l both the Mark I and Mark F reactors operating?

a.

a third individual capable of initiating emergency action present in the Triga Reactors Fr.cility, and an SRO readily available on call-b.

a third licensed inJividual present in the Triga Reactors Facility.and an SRO readily ave.ilable on call c.

an SRO present in the Triga Reactors Facility d.

an SRO readily available on call QUESTION: 015 (1.00)

The Technical Specification minimum pool level for the Mark F reactor is feet above the top grid plate, a.

8

-l b.

10 c.

14 l

d.

16 h

4 i

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B., NORMAL /EMERG PROCEDURES & RAD CX)N

,[

P2g3 20

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l QUESTION: 016 (1.00)

Which one of the following is an action that should be taken if the Mark F e

raaetor's bulk rool temperature reaches 40 degrees C during an. extended operation?

a.

No action is required until the 65 degree C bulk pool temperature limit is reached, b.

The reactor should be shutdown, and the PIC should be notified.

c.

The water treatment system should be turned off.

d.

The coolers normally used for the Mark I reactor should be shifted,to i

the Mark F reactor.

l QUESTION: 017 (1.00)

According to the Mark I Reactor's Technical Specifications, the reactivity worth i

of any individual experiment shall not exceed

, and the total absolute rsactivity worth of a combination of experiments shall not exceed l

a.

$1.00: $3.00 b.

$3.00; $4,00 c.

$3.00: _$5.50 e

i d.

$3.25; $5,00 l

1

(***** CATEGORY B CONTINUED ON NEXT PAGE_*****)

w u.

riunnnL/sntnu envusvunto a nna vui.

.aav..

t

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QUESTION:-018 (1.00)

One step in the Mark I reactor's Alarm and Scram Procedure for a " Failure of the Control Rods to Drop on a Scram" directs you to secure console power,-but then to restore it if securing it did not effect a scram. Which one of the following is the reason power should be restored to the console?

a so that the radiation monitors will still function-b.

so that fuel temperature can still be monitored c.

so that the conductivity monitors will still function d.

so>that the power channels can still be monitored QUESTION: 019 (1.00)

A reactor control rod reactivity worth calibration is beingiconducted using the

" bump period method" in accordance with the Mark I Standard Operating Procedures.

The REG rod being calibrated has been withdrawn in SIX equal reactivity increments to go from fully inserted to fully withdrawn. After EACH withdraws 1 the STABLE PERIOD measured [between 5 watts and 1 KW) was +37 seconds.

Which one of the following is the TOTAL worth'of this control rod?

]

I a.

$10.05 1

b.

$4.64 c.

$2.64 d.

$1.20 I

(* m

CATEGORY B CONTINUED ON NEXT PAGE *****)

y, l-

.s

\\-

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QUESTION: 020 (1,00)

Following an emergency which required facility evacuation, which one of the following individuals will determine when the facility may be reentered?

l a.

Emergency Coordinator.

b.

Emergency Response and Recovery Director-c.

Emergency Response Team Leader d.

Security Officer 1

l l

(***** END OF CATEGORY B-*****)

C.. PLANT AND RAD MONITORING SYSTEMS Pcg3 23

\\

QUESTION: 001 (1.00)

Self protect 1 1 refers to fuel that a.

has a negative fue erature coefficien b.

has built in burnable poi.*

c.

has an exte ose rate < 1000 Rem /hr with tervening shielding contains uranium enriched above 20 weight percent QUESTION: 002 (1.00)

Which one of the following correctly describes the location where the water treatment system takes suction from the reactor pool, and the reason this location is used?

a.

from the upper region to limit siphoning of pool water in case of system leakage b.

from the upper region to allow N-16 gammas time to decay before the water enters the treatment system c.

from the core region so N-16 gammas will enter the water treatment-system rather than becoming a radiation hazard at the pool surface d.

from the core region so impurities will be filtered out before they become irradiated l

l

(*4*** CATEGORY C CONTINUED ON NEXT PAGE *****)

c.

C. -. PLANT AND RAD MONITORING SYSTEMS Paga 24

\\.

t L

QUESTION: 003 (1.00) i Which one of the following statements best describes'the purpose of the diffuser system on the Mark F reactor?

a.

it enhances the natural circulation flow in the pool b.

it creates turbulence in the pool to dissolve N-16 before it rises to l

the pool surface c.

it provides additional decay time for N-16 before it rises to the pool l

surface

?

d.

it deaerates the pool water to reduce the formation of Ar-41 QUESTION: 004 (1,00)

Which one of the folowing color combinations would be displayed on the Mark I high resolution CRT for a standard control rod and drive that are completely withdrawn with the magnet making contact?

ROD color MAGNET BOX a.

grey black 1

b.

magenta yellow c.

green yell;w d.

magenta b1hek 1

(***** CATEGORY C CONTINUED ON NEXT PAGE **m)

C.

PIANT AND RAD MONITORING SYSTEMS l

Page 2b

-\\

8

+

I QUESTION: 005 (1.00)

While operating the Mark I reactor at 50 KW the operator accidentally pushes _and immediately releases the MAGNET pushbutton for the REG rod.

Which one of the following is the correct response of the reactor control system 7-a.

all rods scram b.

only the REG rod scrams c.

the REG rod momentarily drives inward until the pushbutton is released d.

the YELIIM color in the MAGNET box win momentarily be eliminated but-the REG rod will not move l

QUESTION: 006 (l.00)

While the Mark I reactor is operating in the automatic mode, the actual power.

input used by the servo system to adjust power to the demanded level is provided by a.

the NM-1000 channel b.

the NP-1000 channel-i the NPP _1000 channel c.

d.

the highest reading channel 4

QUESTION: 007 (1.00)

Loss of the mma compensating signal to a compensated ion chamber will result in which one of the following?

a.

a sudden increase in indicated power at' low power b.

a sudden decrease in indicated power ~at. low power

~

c.

a sudden increase in indicated power at high power d.

a sudden decrease in indicated power at high power

.(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

i

C.

. PLANT AND RAD MONITORING SYSTEMS l

Page 26

\\

l l

l QUESTION: 008 (1.00) l l

l Which one of the following will be the response of the Mark F reactor if while I

operating at 1000 KW the K1 power channel fails high?

a.

The reactor will scram because the K1 channel has exceeded the scram l

setpoint, b.

The reactor will continue operating because the K1 channel provides startup indication but no scram function, c.

The reactor will continus operating because the required 2 of 3 logic for a reactor scram has not been met. a d.

The reactor will continue operating because the required 2 of 4 logic for a reactor scram has not been met.

QUESTION: 009 (1.00)

Which one of the following describes how gamma compensation is accomplished in the Mark F reactor's K3 power channel?

l l

a.

A pulse height discriminator is used to eliminate the gamma signal.

1 l.

b.

A Campbelling circuit is used to eliminate the gamma signal.

l l

c.

A compensated ion chamber is used to eliminate the gamma signal.

l l

d.

Compensation is not required at the power levels monitored by the K3 channel.

i I

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

m Q.. PLANT AND RAD MONITORING SYSTh 4

Paga 27

\\

5 QUESTION: 010 (1.00)

Which one of the following describes the rate of power change for the Mark I raaetor while operating in the automatic mode?

l a.

Power changes on a fixed preset period of 5.0 seconds.

b.

Power changes on a fixed preset period of 6.5 seconds.

c.

Power changes on a variable period automatically determined by the magnitude of the desired power change l

l d.

Power changes on a variable period maritally set by the operator.

QUESTION: 011 (1.00)

Which one of the following devices is used to reduce the bottoming impact of a Mark I reactor control rod after a reactor scram?

a.

a water dashpot devico 1

b.

an air dashpot device c.

a mechanical shock absorber l

l d.

the rod compression spring QUESTION: 012 (1.00)

Which one of the following conditions will cause an automatic scram of the Mark I reactor?

a.

NP-1000 channel reading 250 KW b.

reactor period of 3 seconds c.

NPP-1000 high voltage power supply momentarily decreases 5%

d.

fuel temperature reading 750 degrees C

(***** CATEGORY C C)NTINUED ON NEXT PAGE *****)

- Q..PIANT AND RAD MONITORING EYSTEMS i-P g) 28

\\

s QUESTION: 013 (1.00)

On a sustained loss of electrical power to the TRIGA Reactors Facility, which one of the following components will be powered by the Uninterrupted Power Supply (UPS)?

a.

Mark F wide range power channel b.

Mark I NPP-1000 and NP-1000 power channels c.

Mark I and Mark F radiation area monitors i

d.

Mark I and Mark F continuous r.onitors l

l QUESTION: 014 (1.00)

Which one of the following conditions will-automatically activate the evacuation alarm?

a.

Ono RAM alarming at the high alarm setpoint, b.

Two RAMS alarming at the low alarm setpoint, c.

Two RAMS alarming, one of which must be a-high alarm.

d.

The CAM alarming at 10,000 cpn, i

1 i

QUESTION: 015 (1.00) l How does the rod control ayatem adjust power 'in the automatic mode of operation?

4 a.

By movements of the regulating, shim, and safety control. rods.

I b.

By movements of the regulating and safety control rods, c.

By movements of the regulating and shim contro1Lrods.

l d.

By movement of the regulating control rod only.

s

(****'* CATEGORY C CONTINUED ON NEXT PAGE *****)

il

)

U.

j'lANT ANL) hall MUNITVKINU bYbThMS l

t'ags 40

\\\\'

QUESTION: 016 (1.00) c In the eve.it of a leak from a fuel element during full power operation, what are the PRED0'.flNANT isotores that will be detected by the continuous air monitor?

a.

nf.trogen-16 and argon-41 l

b.

lission product gasses (Kr-88 and Xe-135) c.

fission product iodine (I-131 and I-133]

5.

fission product daughters (Rb-88 and Cs-139) w QUESTION: 017 (1.00)

How does the transfer system function to MINIMIZE. contamination while inserting and removing samples from the terminus in the core?

a.

The blower exhausts through a filter into the reactor room exhaust duct and pressurizes the system to move the sample into and out'of the j

terminus, b.

The blower exhausts through a filter into.the reactor room exhaust duct-and draws a vacuum on the system to move the sample into and out_of' the terminus.

l c.

The blower draws air through a filter from the: reactor room exhaust duct and pressurizes the system to move the sample into and out of.the

terminus, d.

The blower draws air through a filter. from the reactor room exhaust duct and draws a vacuum on the system to move the sample into and out of the terminus.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

l C..PIANT AND FAD MONITORING SYSTEMS Page 30 a

QUESTION: 018 (1.00)

Which one of the following detector types is utilized by the criticality alarm?

a.

Geiger counter l

b, scintillation detector c.

proportional counter d.

ionisation chamber i

QUESTION: 019 (1,00)

Which one of the following is the approximate worth of'a standard control rod?

a.

$1.00 b.

$2,00 c.

$3.00 d.

$4.00 l

QUESTION: 020 (1.00)

Which one of the following statements correctly describes the automatic actions that will occur if the radioactivity monite-

.c the Mark.I ventilation system obsolute filter reaches a radiation level c; G mr/hr while the reactor is.

operating?

l a.

no automatic action will occur until the 10 mr/hr setpoint is reached l

b.

an audible alarm and light-will be activated in the Mark I control room l

c.

the ventilation system will be isolated d.

the reactor will scram and the ventilation system will be isolated I

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION ***+ n***t) i

.A,

.RX THEORY-, THERM 0 & FAC OP CHARS' I

F2g2 J1

~

\\

h ANSWER:

001 (1.00) b REFfRENCE:

GA Reactor Training Manual (p. VI-3)

ANSWER:

002 (1.00) d i

REFERENCE:

GA Reactor Training Manual ( p.VI-8,9 ).-

-r ANSWER:

003 (1.00) b

REFERENCE:

GA Reactor Operator Training Manual (p. VI-10)_

j l

ANSWER:

004 (1.00) l l

6 l

REFERENCE:

r GA Reactor Operator Training Manual (p. VI-9)

ANSWER:

005 (1.00) b

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

i

y

.- 4..RX THEORY THERMO & FAC OP CHARS

,j h ga-32

\\

NEFERENCE:

GA Reactor 0;erator Training Manual (p. VI-9) l ANSWER:

006 (1.00) b

t GA Reactor Operator Training Manual

.(p. VI-7) l l

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

1-l.

l l

e

' 4. RX THEORY. THERMO & FAC OP CHARS i-Pcg> 33-

\\

ANSWER:

010 (1.00) e

REFERENCE:

GA Reactor Operator Training Manual (p. VI-15)

.l I

=r ANSWER:

011 (1.00) i b

REFERENCE:

GA Reactor Operator Training Manual (p. VI-15)

-. 3 ANSWER:

012 (1.00) b

REFERENCE:

GA Seactor Operator Training Manual-(p. VI-16) l t'

ANSWER:

,013 (1.00)

C

REFERENCE:

GA Reactor Operator Training Manual- (p. I-16, VI-7)

I

(***** CATEGORY A CONTINUED ON.NEXT PAGE *****)

o A.

RX. THEORY. THERMO & FAC OP CHARS P ga 34

\\-

t t

ANSWER:

014 (1.00) c

')

REFERENCE:

l' GA Reactor Operator Training Manual (p. 1-15, VI-18)

I i

ANSWER:

015 (1.00) d

REFERENCE:

GA Reactor Operator Training Manual (p. VI-9,-VI-18) s i

ANSWER:

016 (1.00) b

REFERENCE:

GA Reactor Operator Training Manual -(p.I-16)

ANSWER:

017 (1.00) b

REFERENCE:

GA Reactor Operator Training Manual (p. VI-19) i ANSWER:

018 (1.00) l a

w 1

1

(

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

s,.

A.,RX THEORY, THERM 0 & FAC OP CHARS i

P:g2 35 N

8 kEFERENCE:

GA Reactor Operator Training Manual (p. VI-15)

ANSWER:

019 (.s0)

~I a

REFERENCE:

{

GA Reactor Operator Training Manual (p. 1-32, VI-29, VI-31)-

ANSWER:

020 (1.00) c EEFERENCE:

GA Supplementary Material'(IV: XI-1)

GA Reactor Operator Training Manual (p. 6-2 to 6-16) 1.f

[

l l

4

'l>

(***** END OF CATEGORY A'*****)'

v, t

B. NORMAL /EMERG PROCEDURES & RAD CON Pcg3 36

(

\\-

ANSWER:

001 (1.00) b

REFERENCE:

GA Supplementary Material (p.III-27)

I T

ANSWER:

002 (1.00)

G

REFERENCE:

GA Supplementary Material (IV: p. I-4) i ANSWER:

003 (1.00) e

REFERENCE:

GA Supplementary Material (III: p.4) 1 ANSWER:

004 (1.00) nEFERENCE:

l GA Supplementary Material (IV: p.I-2).

ANSWER:

005 (1.00) l b

.o

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

k

B.

. NORMAL /EMERG PROCEDURES & RAD. CON i

Pega 37

(

A NEFERENCE:

GA Supplementary Material (IV: p. 1-2)

ANSWER:

006 (1.00) i d

REFERENCE:

GA Supplementary Material (III-19)

ANSWER:

007 (1.00) b

REFERENCE:

GA Supplementary Material (V-1)

.i ANSWER:

008 (1.00)

C

REFERENCE:

GA Supplementary Material (VI: V-2)

ANSWER:

009 (1.00) c

-l l

l l

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)-

s,

B. ' NORMAL /EMERG PROCEDURES & RAD CON' f~

--pig > 38.

~

s

.g h

kEFERENCE:

GA Reactor Operator Training Manual (p.I-32)'

GA Technical Specifications (I: p.5, II: p.3) l ANSWER:

010 (1.00) b

REFERENCE:

l GA Reactor Operator Training Manual (V-27)

.s ANSWER:

011 (1.00) b

REFERENCE:

GA Reactor Operator Training Manual (p.-V-28) l

- i ANSWER:

012 (1.00) l d

REFERENCE:

1 GA Supplementary Material (IV: VIII-2)

~~

' ANSWER:

013 (1.00) c

REFERENCE:

i GA Mark I-Technical Specifications'(p.19),

r

(***** CATEGORY B CONTINUED ON-NEXT PAGE :*****)

9

t 5.

. NORMAL,/EMERG PROCEDURES & RAD 00N

{

Ftge 39 i

1

\\

t ANSWER:

014 (1.00) r d

r

REFERENCE:

GA Supplementary Material (IV:

1-1)

/J1SWER:

015 (1.00)

L d

REFEP.ENCE:

GA Mark F Technical Srecifications (p. 3)

ANSWER:

016 (1.00) e

REFERENCE:

GA Supplementary Material (V:

1-4)

ANSWER:

017 (1.00) b

REFERENCE:

GA Hark I Reactor Technical Syecifications (p.11) 4 l

l ANSWER:

018 (1.00) d

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)'

s.

B. oNORMAL/EMERG PROCEUJRES & RAD 00N Page 40

\\

.3 RE3RENCE:

GA Supplementary Material (IV: VI-7)

ANSWER:

019 (1.00) d

REFERENCE:

i GA Supplementary Material (IV:

IX-1) nNSWER:

020 (1,00) 3 b

REFERENCE:

GA Supplementary Material (III: p.14) i l

1 e

(***** END OF CATEGORY B *****)

i t

3

p.

PLANT AND RAD MONITORING SYSTRMS

,i P:ga 41

\\

i

~ ISWEP.:

001 (1.00) i

)c,ggjd c

REFERENCE:

GA >upplementary Material (III:

2)

ANSWER:

002 (1.00) a

REFERENCE:

GA Reactor Operator Training Manual (I-33)

ANSWER:

003 (1.00)

C

REFERENCE:

GA Reactor Operator Training Manual -(I-32)

ANSWER:

004 (1.00) 1

REFERENCE:

I GA Reactor Operator Training Manual (11-26) l l

ANSWER:

005 (1.00) l l

b j

( ***** CATEGORY C CONTINUED ON NEXT PAGE *****)

I l

GA Reactor Operator Training Manual (V-5)

ANSWER:

017 (1.00) l b

~

REFERENCE:

GA Reactor Operator Training Manual (I-41)

ANSWER:

018 (1.00) d t

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

1

?

C. ' PLANT AND RAD MDNITORING SYSTEM 3 P:ge 45 s

REFERENCE:

GA Reactor Operator Tra hing Manual (V-20)

ANSWER:

019 (1.00) b

REFERENCE:

GA Reactor Operator Training Manual (I-23)

ANSWER:

020 (1.00) b

REFERENCE:

GA Reactor Operator Training Manual (1-37, 2-33) l

(***** END OF CATEGORY C *****)

(**++******

END OF EXAMINATION **********)

,A.

RX THEORY, THERM 0 & FAC OP CHARS Pag] 1 ANSWER S H E E 'l Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the Mank.

001 a

b c

d 002 a

b c

d 003 a

b c

d 004 a

b c

d 005 a

b c

d 006 a

b c

d j

007 a

b c

d 008 a

b c

d 009 a

b c

d 010 a

b c

d 011 a

b c

d l

012 a

b c

d 1

013 a

b c

d 014 a

b c

d 015 a

b c

d 016 a

b c

d l

017 a

b c

d 018 a

b c

d 019 a

b c

d 020 a

b c

d l

i l

(***** END OF CATFORY A *****)

I

E.

HORMAL/EMERU PROCEDtJRES & RAD 00N P:g) 2 ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

l 001 a

b c

d 002 a

b c

d 003 a

b c

d 004 a

b c

d 005 a

b c

d 006 a

b c

d i

007 a

b c

d 008 a

b c

d 009 a

b c

d 010 a

b c

d 011 a

b c

d 012 a

b c

d 013 a

b -

e d

014 a

b c

d 015 a

b c

d 016 a

b c

d 017 a

b c

d 018 a

b c

d 019 a

b d

020 a

b o

d

(***** END OF CATEGORY B *****)

,k. *RX THEORY. THERM 0 & FAC OP CHARS Pag) 1

+

ANSWER KEY 001 b

002 d

003 b

004 a

005 b

006 b

007 d

008 e

009 a

010 c

011 b

012 b

013 a

014 c

015 d

016 b

I 017 b

018 a

019 a

020 e

l

(***** END OF CATEGORY A *****)

,f.

NORMAL /EMERG PROCEDURES & RAD CON Paga 2 4

ANSWER KEY 001 b

002 a

003 e

004 b

005 b

006 d

007 b

008 o

009 e

010 b

l 011 b

012 d

l 013 e

014 d

l 015 d

016 c

l 017 b

018 d

019 d

020 b

(***** END OF CATE00RY-.B *****)

. ' PLANT AND RAD MONI70 RING SYSTEMS Pag) 3 I

ANSWER KEY 6ekled,/

^^1 v

GA v

002 a

003 e

004 b

i 005 b

006 a

007 a

008 c

009 d

010 b

011 a

012 d

013 a,b l

014 e

015 d

016 d b j

017 b

018 d

019 b

020 b

(***** END OF CATEGORY C *****)

( ********** END OF EXAMINATION ********** )

!

ML20062G293

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